This postdoctoral position is part of the project eMEANSS (Enhanced Methodologies for Advanced Nuclear System Safety) (https://gow.epsrc.ukri.org/NGBOViewGrant.aspx?GrantRef=EP/T016329/1), which aims to develop a multi-disciplinary framework for uncertainty quantification in key areas of nuclear engineering, including structural integrity. You will undertake research on in situ studies of the interactions between cyclic load and temperature (up to 1000°C) in nuclear graphite, which will support non-linear finite element modelling of the performance of reactor core components in high temperature reactors.

 

With a background in high temperature testing of materials, you will be self-motivated, able to plan and deliver a research project. You will have a PhD (or be near completion) in related topics and experience in synchrotron X-ray diffraction and digital image correlation.

 

This position is available immediately and is fixed-term until 13 January 2025.

 

The eMEANSS project aims to develop a multi-disciplinary framework for uncertainty quantification that enables its identification and impact in three key areas of nuclear engineering: reactor physics, structural integrity and fuel performance. Working in collaboration with our partners, we are focussed on fatigue failure of graphite components, especially at high service temperatures, which is of concern for next generation reactors. A design tool is needed that can efficiently incorporate variances in the mechanical and thermal loading history, and material properties to quantify a probable component life. These interact in graphite as mechanical damage introduces micro-cracking that impacts elastic properties and the subsequent development of damage from applied strains. In addition to the simple uncertainties in boundary conditions, i.e. external load, internal stress and thermal conditions, complications arise from both the load sequence and the temperatures at which loading occurs, coupled with the impacts arising from neutron irradiation, temperature and coolant interactions on the relationship between deformation and graphite properties. We aim to generate new knowledge on the high temperature cyclic response of advanced nuclear graphite and will utilise it in the development of a new probabilistic modelling framework. In particular, the sensitivity of lifetime predictions to input data will be quantified, and practical guidelines will be proposed for inspection strategies that may be adopted in future high temperature reactors.

 

All applications must be made online using the Oxford University E-Recruitment system, no later than 12 noon on 6 August 2024. You will be required to upload a CV and a Supporting Statement as part of your application. Please do not attach any manuscripts, papers, transcripts, mark sheets or certificates as these will not be considered as part of your application.

Interviews are scheduled to take place at the Department of Materials on 23 August 2024 and you must be available on this date, either by Teams, Zoom or in person. Please note in normal circumstances only interview travel expenses within the UK will be reimbursed.